| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Assessment of Ring and Axial Tension Tests for Determining Cladding Mechanical Properties |
| Author(s) |
Robert Hansen, Philip G. Petersen, Prasenjit Dewanjee, Aaron W. Colldeweih, Jake A. Stockwell, David W. Kamerman, Fabiola Cappia |
| On-Site Speaker (Planned) |
Robert Hansen |
| Abstract Scope |
Fuel cladding for nuclear power reactors serves as the barrier between fuel and primary coolant, and mechanical properties of cladding are of particular interest. However, cladding concepts such as zirconium-based alloys used in light water reactors (LWRs) are anisotropic. Directional tests which probe hoop and axial material behavior have been developed and implemented to address the unique geometry constraints of testing tubular materials. This work investigates these tests for suitability in remote hot cell tests of irradiated cladding through a series of out-of-cell tests paired with digital image correlation (DIC). Multiple versions of each test method are considered, and recommendations are given for the methods providing the best accuracy and results when limited by remote hot cell constraints required to test irradiated cladding. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Other |